Detail of "12340-54-4"

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Effect of metallurgical structure on the nature of irradiation damage in a zirconium alloy: Effect of metallurgical structure on the nature of irradiation damage in a zirconium alloy. Northwood, D. O.; Bahen, L. E.; Fleck, R. G. (Chalk River Nucl. Lab., At. Energy Canada Ltd., Chalk River, Ont., Can.). J. Nucl. Mater., 66(1-2), 209-11 (English) 1977. CODEN: JNUMAM. DOCUMENT TYPE: Journal CA Section: 71 (Nuclear Technology) Section cross-reference(s): 56 The irradn. damage in Zr-1.15Cr-0.1 wt.% Fe alloy [11134-24-0] was evaluated, and the reason was detd. for the low creep rates in material which contains a fine ppt. The thermomech. histories, resultant structures, and in-reactor creep rates of the alloy, treated in 3 different ways, were studied. The specimens were irradiated, in stress relaxation holders, for 5333 h at .apprx.570 K to a fluence of 3.84 .times. 1024 n/m2 (E >1 MeV). The low creep rates must occur because dislocation glide is impeded by the fine ppts. by a pptn. hardening mechanism. For pressurized-water reactors, which operate at .apprx.570 K, five ppts. of ZrC2 [12340-54-4] formed by aging at 623 K are suitable hardeners, because there was no detectable change in size or d. after irradn. at 570 K for 5333 h. The creep resistance of the alloy probably could be further improved by increasing the amt. of alloy addn. in solid soln.